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The Development of Small Area Socioeconomic Data to be Utilized for Impact Analysis: Rural Southern Nevada
This paper describes the process by which economic and demographic estimates and projections will be prepared to determine the potential economic and demographic impacts that may result...

Beyond NEPA: A Look at Socioeconomic Impact Assessments Required Under the Nuclear Waste Policy Act, as Amended
The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) has been charged by Congress, through the Nuclear Waste Policy Act, as amended (the Act),...

Hedonic Price Theory: Concept and Applications
Direct and indirect techniques are being used to estimate economic consequences of proximity to existing or proposed public facilities. The hedonic price theory, an indirect technique,...

The Role of Sensor Directed, Model-Based Control in Robotic Handling of Nuclear Waste Casks and Materials
This paper discusses the results from several projects at Sandia National Laboratories investigating the application of intelligent machine technologies to remote handling of nuclear waste...

Spent Fuel and High-Level Waste Management in Selected Countries: Trends and Issues
This paper contains descriptions of the major parameters and plans for management of spent nuclear fuel and high-level radioactive wastes in Belgium, Canada, France, the Federal Republic...

Spent Fuel Storage Requirements for Nuclear Utilities and OCRWM
Projected spent fuel generation at U.S. power reactors exceeds estimated aggregate pool storage capacity by approximately 30,000 metric tons of uranium (MTU). Based on the current repository...

Site Selection Criteria for Constructing an Independent Spent Fuel Storage Installation (ISFSI) at a Commercial Nuclear Power Plant
Commercial nuclear power plants in the U.S. are responsible for providing their own interim storage for excess spent fuel. A facility located onsite, acting as a buffer between in-pool...

Choosing AT-Reactor Spent Fuel Storage Technologies
Need for expansion of the spent fuel storage capability of reactor sites was first caused by delays in construction of reprocessing facilities, later by cessation of commercial reprocessing...

Concrete Cask Storage Technology
The paper presents the design and operation of the new dry storage system for nuclear waste. The system was designed by complete nuclear, thermal-hydraulic and structural analysis to the...

Comparative Analyses of Spent Nuclear Fuel Transport Modal Options
The movement of nuclear waste can be accomplished by various transport modal options involving different types of vehicles, transport casks, transport routes, and intermediate intermodal...

Optimizing the Spent Fuel Transportation Cask for Spent Fuel Age and Burnup: A Preliminary Analysis
The U.S. Department of Energy (DOE) has been assigned responsibility for managing the nation's spent nuclear fuel (SNF). Because of the large quantity of SNF to be moved,...

Transportation Cask Life Cycle Cost Uncertainty Analysis
This paper demonstrates an uncertainty analysis methodology using random sampling. This methodology has been applied to a nuclear waste transportation code, and several transportation...

Size and Transportation Capabilities of the Existing U.S. Cask Fleet
This study investigates the current spent nuclear fuel cask fleet capability in the United States. In addition, it assesses the degree to which the current fleet would be available, as...

Analysis of RADTRAN Transportation Model
The RADTRAN computer model, used to estimate the risks of transporting waste to a high-level repository, is critically reviewed. Ignoring high consequence accidents, human error, sabotage,...

Accident Analyses in Fulfillment of the Requirements of the National Environmental Policy Act and Their Relationship to the Packaging and Testing Requirements of the Nuclear Regulatory Commission
In planning its Transportation Program, the Office of Civilian Radioactive Waste Management must address two fundamental questions: (1) To what extent are the reasonably foreseeable significant...

Properties of the West Valley Waste Form
The centroid composition of the West Valley Demonstration Project waste form has been selected on the basis of criteria mandating high chemical durability and good processibility. A review...

Vapor Hydration and Subsequent Leaching of Transuranic-Containing SRL and WV Glasses
High-level nuclear waste glass that is subject to disposal in the proposed unsaturated environment at Yucca Mountain, Nevada, initially will be altered through contact with humid air....

Recent Results on the Effect of Gamma Radiation on the Durability and Microstructure of DWPF Glass
The effect of gamma radiation on the durability and microstructure of a simulated nuclear waste glass from the Savannah River Site has been carefully investigated. Three large pieces of...

Soluble High-Level Waste Decontamination and Disposal at the Savannah River Site
The high-level radioactive waste that has accumulated at the Savannah River Site is stored in large underground steel tanks. Programs to remove the soluble waste from the storage tanks,...

Volatilization of Cesium and Ruthenium From High-Level Waste Glass
The contamination of the air above high-level waste glass by ¹³⁴Cs, ¹³⁷Cs and ¹⁰⁶Ru...

 

 

 

 

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